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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Todd K. Campbell, Edgar Robert Gilbert, Cheryl Knox Thornhill, Bernard J. Wrona
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 182-195
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34186
Articles are hosted by Taylor and Francis Online.
To support dry storage technology, oxidation tests were conducted with light water reactor spent fuel. The initial rate of weight gain for spent fuel was up to 50 times greater than the initial rate for nonirradiated pellets. Spent fuel formed measurable U4O9+x particulates at weight gains significantly higher than those at which the nonirradiated pellets formed U3O8 powder. Initial test results on three types of pressurized water reactor (PWR) spent fuel indicated that fuel type had a significant influence on weight gain. Additional tests were performed at temperature levels from 135 to 230°C on fuel with burnups from 8 to 34 GWd/ tonne U irradiated in five different reactors. The tests were conducted in static air at controlled moisture levels in a 105 R/h gamma field. In the 230°C tests, weight gains for PWR and boiling water reactor (BWR) fuels exceeded 4 wt% after 4000 h of exposure. Powder formation time on BWR fuels increased with increasing burnup; weight gain magnitudes were independent of fuel burnup.
